text
NRC r X4 300 U.S. NUCLEAR REGULATURV COMMISSION APPROVED BV OM8 Nu. 3150 0104 (542; EXPIRES 5/31/95 EST! MATED BURDEN PER PESPONSE D COMPLY WITH NRNNIfh)C0ggggg;0gSgATE LICENSEE EVENT REPORT (LER)
- [
0 THE INFORMATICN AND RECORDS MANAGEMENT BRANCH (MN2B 7714), L.5. NUCLEAR REGULATORY COMMISSICN.
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WASHINGTON. C:
PROJ;jj5-0001 AND TO T4 PA;ERWORK 2
REDUCTION a.:
(3150 01C4).
r u FICE OF MANA7 M;NT AND M G T WA W INF, TON ? 20 9 FMCILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Limerick Generating Station, Unit 1 05000 352 1 OF 3 TITLL (4) Wo Seperate keactor Water Glean-up (RWGU) Isolations, Engineered Satety Features, Caused by 1.ifting of a Filter Demineralizer Pressure Safetv Valve EVENT DATE ($)
LER NUMBER (6)
REPORT DATE (7)
OTHER F ACILITIES INVOLVED (8)
SEQUENTIAL REVISION MH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER 05000 tALlLiii NAMt DOCNEI NUMBER 03 11 97 97 005 01 06 09 97 05000 OPEPATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6:
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MNt iELir'nuNt NUMcEk (tr.cluCe Area LOGE)
J. L. Kantner - Manager, Experience Assessment, LGS (610) 718-3400 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 0 E
0 E
CAUSE
SYSTEM COMPONENT MANUFACTURER
CAUSE
SYSTEM COMPONENT MANUFACTURER SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED YES SUBMISSION NO
'f yes, cc plete E/;ECTED SUBMISSION DATE).
)(
DATE (15)
(
ABSIPX,I t L =1; ic A u spaces.
t approximately it single-spacec tyDewritten lines) (16)
On 03/11/97, at 2209 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.405245e-4 months <br /> and 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, 2 separate Primary Containment and Reactor Vessel Isolation Control System (PCRVICS) actuations initiated, Engineered Safety Features, causing Reactor Water Cleanup (RWCU) system isolations.
The 2 PCRVICS actuations were initiated by high differential flow conditions.
An investigation revealed the high differential flow occurred when the pressure safety valve, PSV-045-1-62B, for
'B' RWCU filter demineralizer lifted.
On 03/13/97, the PSV was replaced and the RWCU system was restored.
There were no adverse consequences and no radioactive material was released to the environment as a result of this event. The appropriate RWCU filter demineralizer-PSVs will be monitored to determine it a generic concern exists.
Any findings, including the potential need to replace these PSVs on an established frequency, will be addressed as necessary.
9706170182 970609 PDR ADOCK 05000352 S
PDR
U.S. NUCLIAR kE'5UI.ATORY ComISSION APPROVED BY OMB NO. 3 40 0104 NRC FO 366A EXPIRES 5/31/15 (5-92) i E5 IMATED BURDEN PER RESPONSE TO COMPLY WITH S INFORMATION COLLECTION REQUEST: 50.0 HFS.
F WD C0mENTS REGAROD4G BURDEN ESTif' ale TO i
LICENSEE EVENT REPORT (LER)
THE INFORMATION ANf) RECORUS MWGEENT BRANCH i
TEXT CONTTEATION g g g f g,RE g T0R g g 9
OFFICE OF REDUCTICN PM)ECT (3150 0104). DC 20603 HMAGEMENT AND BUDGET WASHINGTON.
FACILITY NAME (1)
DOCKET NUMBER (2)
LER NlniiER (6) l PAGE (3)
YEAR SE00ENTIAL REVI5ICN 05000 2 0F 3 I
Limerick Generating Station, Unit 1 352 97
-- 005 --
01
(
TEXT Ut tir>re space as requtrea. use coatttonas copies or MC form J00A) (11 )
I i
Unit Conditions Prior to the Event:
{
Unit 1 was in Operational Condition 1 (Power Operation) at 100% power j
level.
There were no structures, systems, or components out of i
service that contributed to this event.
The
'A' and
'C' Reactor Water Cleanup (RWCU, EIIS:CE) pumps and the
'B' filter demineralizer were in service.
)
Description of the Event:
I On March 11, 1997, at 2209 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.405245e-4 months <br /> and 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, 2 separate Primary i
Conteinment and Reactor Vessel Isolation Control System (PCRVICS, EIIS:JM) actuations initiated, Engineered Safety Features (ESF),
causing RWCU system isolations.
While restoring the
'A' RWCU filter demineralizer to service following filter regeneration, an.tsolation i
of the RWCU inboard Primary Containment (PC) valve occurred from high
(
differential flow.
The system was re-aligned and a walkdown identified no abnormalities.
The isolation signal was reset and the system was re-started.
Following start of the
'A' RWCU pump, a high differential flow annunciator alarmed and the inboard and outboard PC valves isolated.
The system was secured and an investigation l
revealed the pressure safety valve, PSV-045-1-62B, for the
'B' RWCU filter demineralizer had lifted.
On March 11, 1997, Operations personnel reset the second PCRVICS isolation signdl.
The PSV was replaced and by 0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br /> on March 13, 1997, the
'A' RWCU pump and
'A' filter demineralizer were returned to service.
tl At 0028 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> on March 12, 1997, a 4-hour notification was made to l
the NRC per 10CFR50.72 (b) (2) (ii), since tLis event resulted in automatic ESF actuation 3.
This report is submitted in accordance l
with 10CFR50.73 (a) (2) (iv).
l Analysis:
The consequences of this event were minimal and there was no release of radioactive material to the environner.t.
The RWCU system isolated l
in response to high differential flow initiated by the lifted PSV.
l The reactor water purity remained within the limits specified by Technical Specifications during this event.
Cause of the Event
The 2 RWCU system isolations were initiated by high differential flow conditions caused by lifting of the
'B' RWCU filter demineralizer
.~
(
NRC f 0RM 366A U.5, NUCdAR REGULATOR 7 COMM15510N APPROVED BV OMB NO. 340 0104 EXPIRES 5/31/9$
(5 92)
ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD C0tNENTS REGARD]NG BURDEN ESTIMATE TO LICE 1TSEE EVENT REPORT (LER)
THE INFORMATION AND RECORDS MANAGEMENT BRANCH l
TEXT CONTINUATION (MNBB 7714). U.S. NUCLEAR REGULATORY COMMISSION.
l WASHINGTON. DC 20555 0001, AND TO THE PAPERWORK REDUCTION PR(1]ECT (3150 0104).
OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503 FACILITY NAME (1)
DOCKET NUMBER (2)
U R NUMER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION trMRFA NUMBER 1
05000 3 OF 3 i
Limerick Generating Station, Unit 1 352 97
-- 005 --
01 l
l tex 1 Gt snore space Is requirea. use saatiIanos captes at kkC iorm J00A) (11) l Inf]uent PSV.
1 I
The lifted PSV had been in service since issuance of the Unit 1 1
l facility operating license on October 26, 1984.
A total of 4 of these PSVs operate at the station under this same applicat ion and condition.
No previous failures of these PSVs resulting in PCRVICS l
actuations have occurred.
Corrective Actions
The appropriate RWCU filter demineralizer PSVs will be monitored to determine if a generic concern exists.
Any findings, including the potential need to replace these PSVs on an established frequency, j
will be addressed as necessary.
Previous Similar Occurrences:
None i
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| | | Reporting criterion |
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| 05000352/LER-1997-001-01, :on 841026,failed to Test safety-related Logic Circuits.Caused by Inadequate Test Procedures.Tested & Restored Untested Contacts to Operable Status & Will Revise Appropriate Surveillance Test Procedures |
- on 841026,failed to Test safety-related Logic Circuits.Caused by Inadequate Test Procedures.Tested & Restored Untested Contacts to Operable Status & Will Revise Appropriate Surveillance Test Procedures
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) | | 05000353/LER-1997-001-02, :on 970207,condition Prohibited by TS in That Control Rods Were Removed from Core W/Source Range Monitors Were Inoperable.Caused by Personnel Error.Will Revise pre-outage Training for Affected Personnel |
- on 970207,condition Prohibited by TS in That Control Rods Were Removed from Core W/Source Range Monitors Were Inoperable.Caused by Personnel Error.Will Revise pre-outage Training for Affected Personnel
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1) | | 05000352/LER-1997-002, :on 970123,failed to Perform Required Visual Inspections of Blind Flanges.Caused by Misinterpretation of Surveillance Requirements.Visually Inspected Blind Flanges & Incorporated These Into Surveillance Tests |
- on 970123,failed to Perform Required Visual Inspections of Blind Flanges.Caused by Misinterpretation of Surveillance Requirements.Visually Inspected Blind Flanges & Incorporated These Into Surveillance Tests
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000353/LER-1997-002-01, :on 970212,leakage Was Identified from 2 Inch Reactor Pressure Vessel Instrument Nozzle.Caused by Improper installation.N12B Connection Was Removed & Sent off-site for Analysis |
- on 970212,leakage Was Identified from 2 Inch Reactor Pressure Vessel Instrument Nozzle.Caused by Improper installation.N12B Connection Was Removed & Sent off-site for Analysis
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000352/LER-1997-003, :on 970204,degraded Back Pressure Dampers Needed for Pipe Rupture Mitigation Resulted in Operation Being Outside Design Basis.Caused by Failure to Include Periodic Cycling & Cleaning of Bdps.Addl Failures,Corrected |
- on 970204,degraded Back Pressure Dampers Needed for Pipe Rupture Mitigation Resulted in Operation Being Outside Design Basis.Caused by Failure to Include Periodic Cycling & Cleaning of Bdps.Addl Failures,Corrected
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000353/LER-1997-003-02, :on 970429,several Main Steam Sys Relief Valves Had Setpoint Drifts Due to Corrosion Induced Bonding Between Pilot Disc & Seat.Licensee Is Participating in BWROG Setpoint Drift Committee |
- on 970429,several Main Steam Sys Relief Valves Had Setpoint Drifts Due to Corrosion Induced Bonding Between Pilot Disc & Seat.Licensee Is Participating in BWROG Setpoint Drift Committee
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000353/LER-1997-004-01, :on 930316,failed to Obtain Offgas Sys Grab Sample within Four Hour Interval Required by Ts.Caused by Personnel Error.Analyzed Sample within Following Four Hours, IAW TS & Revised Chemistry Section Sample Program |
- on 930316,failed to Obtain Offgas Sys Grab Sample within Four Hour Interval Required by Ts.Caused by Personnel Error.Analyzed Sample within Following Four Hours, IAW TS & Revised Chemistry Section Sample Program
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1)
10 CFR 50.73(a)(2)(viii)(8) | | 05000353/LER-1997-004, Forwards LER 97-004-00 Re Failure to Obtain Offgas Sys Grab Sample within TS Time Limit on 930316.Delayed Submittal of LER Is Due to Incorrect Assessment of Reportability at Time of Event | Forwards LER 97-004-00 Re Failure to Obtain Offgas Sys Grab Sample within TS Time Limit on 930316.Delayed Submittal of LER Is Due to Incorrect Assessment of Reportability at Time of Event | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1997-004, :on 841026,TS SRs for 10 Fire Rated Assemblies Had Not Been Satisfactorily Met Since Original start-up of Each Unit & 951220.Caused by Inadequate Reviews of Procedures.Procedures Reviewed |
- on 841026,TS SRs for 10 Fire Rated Assemblies Had Not Been Satisfactorily Met Since Original start-up of Each Unit & 951220.Caused by Inadequate Reviews of Procedures.Procedures Reviewed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(1) | | 05000353/LER-1997-005, Forwards LER 97-005-00 Re Plant Transient Which Resulted in Exceeding Licensed Thermal Power by 2.4% on 970605 | Forwards LER 97-005-00 Re Plant Transient Which Resulted in Exceeding Licensed Thermal Power by 2.4% on 970605 | | | 05000353/LER-1997-005-01, :on 970605,facility Operating License Thermal Power Limit Was Exceeded Capacity Due to EHC Function.Cause Unknown.Monitoring Equipment Was Installed on EHC Sys to Provide Info If Similar Tansient Occurs |
- on 970605,facility Operating License Thermal Power Limit Was Exceeded Capacity Due to EHC Function.Cause Unknown.Monitoring Equipment Was Installed on EHC Sys to Provide Info If Similar Tansient Occurs
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) | | 05000352/LER-1997-005-01, Forwards LER 97-005-01 Which Documents Two Separate Unit 1 Primary Containment & Reactor Vessel Isolation Control Sys Actuations.Changes to Corrective Actions Indicated by Rev Bar in Left Hand Margin | Forwards LER 97-005-01 Which Documents Two Separate Unit 1 Primary Containment & Reactor Vessel Isolation Control Sys Actuations.Changes to Corrective Actions Indicated by Rev Bar in Left Hand Margin | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1997-005, :on 970311,two Separate RWCU Isolations Caused by Lifting Filter Demineralizer Pressure Safety Valve.Will Monitor RWCU Filter Demineralizer Psvs to Determine If Potential Need Exists to Replace Psvs |
- on 970311,two Separate RWCU Isolations Caused by Lifting Filter Demineralizer Pressure Safety Valve.Will Monitor RWCU Filter Demineralizer Psvs to Determine If Potential Need Exists to Replace Psvs
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1997-006-01, Forwards LER 97-006-01 Re Discovery That Fire Protection Sys Deluge Valve May Not Have Functioned Per Design Since Issuance of License.Revised LER Provides Cause & Corrective Actions for Event.Changes Indicated by Rev Bars | Forwards LER 97-006-01 Re Discovery That Fire Protection Sys Deluge Valve May Not Have Functioned Per Design Since Issuance of License.Revised LER Provides Cause & Corrective Actions for Event.Changes Indicated by Rev Bars | 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1997-007, :on 970623,HPCI Sys Was Declared Inoperable Due to Clogged Turbine Exhaust Drain Line.Disassembled & Cleaned HPCI Turbine Exhaust Drain Pot Drain Line |
- on 970623,HPCI Sys Was Declared Inoperable Due to Clogged Turbine Exhaust Drain Line.Disassembled & Cleaned HPCI Turbine Exhaust Drain Pot Drain Line
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000352/LER-1997-007-01, :on 970910,isolation of Rwcs Resulting from Lifting of Filter Demineralizer Psv Occurred.Caused by Setpoint Drift.Procedures Revised |
- on 970910,isolation of Rwcs Resulting from Lifting of Filter Demineralizer Psv Occurred.Caused by Setpoint Drift.Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1997-007, Forwards LER 97-007-00 Reporting Unit 1 Primary Containment & Reactor Vessel Isolation Control Sys Actuation Resulting in RWCU Sys Isolation.Rwcu Sys Isolation Was Caused by Lifting of B RWCU Filter Demineralizer Influent Psv | Forwards LER 97-007-00 Reporting Unit 1 Primary Containment & Reactor Vessel Isolation Control Sys Actuation Resulting in RWCU Sys Isolation.Rwcu Sys Isolation Was Caused by Lifting of B RWCU Filter Demineralizer Influent Psv | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1997-008, :on 970726,automatic Closure of Drywell Chilled Water Sys Primary Containment Isolation Valves Occurred. Caused by Failure of Agastat Relay.Dwcs PCIVs Were Reopened & Declared Operable |
- on 970726,automatic Closure of Drywell Chilled Water Sys Primary Containment Isolation Valves Occurred. Caused by Failure of Agastat Relay.Dwcs PCIVs Were Reopened & Declared Operable
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2) | | 05000352/LER-1997-008, Forwards LER 97-008-00 Which Reports Event That Occurred on 841026 Re Failure to Perform Annual Maint Insps of Portable Fire Extinguishers IAW NFPA 10 | Forwards LER 97-008-00 Which Reports Event That Occurred on 841026 Re Failure to Perform Annual Maint Insps of Portable Fire Extinguishers IAW NFPA 10 | | | 05000352/LER-1997-008-01, :on 841026,fire Protection Group Personnel Discovered That Annual Inspection of Fire Extinguishers Had Not Been Performed.Caused by Personnel Error.Will Establish Annual Portable Fire Extinguisher Insps |
- on 841026,fire Protection Group Personnel Discovered That Annual Inspection of Fire Extinguishers Had Not Been Performed.Caused by Personnel Error.Will Establish Annual Portable Fire Extinguisher Insps
| 10 CFR 50.73(a)(2)(i) | | 05000352/LER-1997-009, Forwards LER 97-009-00 Which Documents Event That Occurred at Lgs,Units 1 & 2 on 971015 | Forwards LER 97-009-00 Which Documents Event That Occurred at Lgs,Units 1 & 2 on 971015 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000352/LER-1997-009-01, :on 971015,RM Was Incorrectly Configured.Caused by Personnel Error.Piping at RM Sample Skid Has Been Corrected & Affected Drawings Have Been Revised to Reflect Change |
- on 971015,RM Was Incorrectly Configured.Caused by Personnel Error.Piping at RM Sample Skid Has Been Corrected & Affected Drawings Have Been Revised to Reflect Change
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000353/LER-1997-009, :on 970806,Unit 2 RWCU Isolation Was Initiated. Caused by High Differential Flow Condition.Further Adjustments on RWCU Filter Demineralizer Y-strainer Manual Drain Valves Were Performed |
- on 970806,Unit 2 RWCU Isolation Was Initiated. Caused by High Differential Flow Condition.Further Adjustments on RWCU Filter Demineralizer Y-strainer Manual Drain Valves Were Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2) | | 05000352/LER-1997-010, Forwards LER 97-010-00 Re Condition Outside Design Basis Involving Suppression Chamber Steam Bypass Leakage Path, Which Occurred on 841026 & 890812 | Forwards LER 97-010-00 Re Condition Outside Design Basis Involving Suppression Chamber Steam Bypass Leakage Path, Which Occurred on 841026 & 890812 | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000353/LER-1997-010-01, :on 971107,reactor Vessel Flux Wire Specimen Analysis Was Not Performed IAW TS SR 4.4.6.1.4.Caused by Incomplete Surveillance Tp.Engineering Evaluation Was Performed,Including 10CFR50.59 Review |
- on 971107,reactor Vessel Flux Wire Specimen Analysis Was Not Performed IAW TS SR 4.4.6.1.4.Caused by Incomplete Surveillance Tp.Engineering Evaluation Was Performed,Including 10CFR50.59 Review
| | | 05000353/LER-1997-010, Forwards LER 97-010-00,which Describes Condition Prohibited by TS in That Reflex Wire Specimen from Unit 2 Was Not Examined to Determine RPV Fluence IAW TS Surveillance Requirement 4.4.6.1.4 | Forwards LER 97-010-00,which Describes Condition Prohibited by TS in That Reflex Wire Specimen from Unit 2 Was Not Examined to Determine RPV Fluence IAW TS Surveillance Requirement 4.4.6.1.4 | | | 05000352/LER-1997-011-01, Forwards LER 97-011-01,re Condition Prohibited by TS in That There Was Not Enough Assurance That Valve Would Continue to Meet TS Required Stroke Time When Restoring Valve to Operable Status.No New Commitments Made within Ltr | Forwards LER 97-011-01,re Condition Prohibited by TS in That There Was Not Enough Assurance That Valve Would Continue to Meet TS Required Stroke Time When Restoring Valve to Operable Status.No New Commitments Made within Ltr | 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(1) | | 05000352/LER-1997-011, :on 971025,HPCI Sys Was Rendered Inoperable Due to Closing Turbine Exhaust Line Pciv.Caused by Valve failure.HV-055-1F072 Torque Switch Setting Was Increased within Analyzed Limits |
- on 971025,HPCI Sys Was Rendered Inoperable Due to Closing Turbine Exhaust Line Pciv.Caused by Valve failure.HV-055-1F072 Torque Switch Setting Was Increased within Analyzed Limits
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(1) | | 05000352/LER-1997-012, :on 971120,unplanned Closure of Primary Containment Isolation Valve Occurred.Caused by an Inaccurate Drawing & an Inadequate Partial Surveillance Test. Engineering Change Request Was Initiated |
- on 971120,unplanned Closure of Primary Containment Isolation Valve Occurred.Caused by an Inaccurate Drawing & an Inadequate Partial Surveillance Test. Engineering Change Request Was Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1997-013-01, Forwards LER 97-013-01,re Failure to Adequately Test Control Logic for Various Pcivs.No New Commitments Made within Ltr | Forwards LER 97-013-01,re Failure to Adequately Test Control Logic for Various Pcivs.No New Commitments Made within Ltr | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1997-013, :on 971205,various PCIVs & Other Valves Were Out of TS Surveillance & 3 Were Otherwise Noted Inoperable. Caused by Construction Drawing Error & Personnel Error. Revised Identified Document Deficiencies |
- on 971205,various PCIVs & Other Valves Were Out of TS Surveillance & 3 Were Otherwise Noted Inoperable. Caused by Construction Drawing Error & Personnel Error. Revised Identified Document Deficiencies
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1997-014, :on 971222,RHRSW Sys Pump Tripped Due to Spurious Trip Signal Generated by B Radiation Monitor. Replaced Preamplifier Cable for B Radiation Monitor, Cleaned Signal Connectors & Generated CM Action Request |
- on 971222,RHRSW Sys Pump Tripped Due to Spurious Trip Signal Generated by B Radiation Monitor. Replaced Preamplifier Cable for B Radiation Monitor, Cleaned Signal Connectors & Generated CM Action Request
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|
